A steady state superconducting tokamak SST1, is being designed at Institute for Plasma Research, Bhat, Gandhinagar, INDIA. The toroidal and poloidal magnetic field coils for this tokamak are made from NbTi based superconducting cable - in - conduit conductor and will be maintained at 4.5 K during operation. The toroidal field (TF) coils produce a field of 3.0 Tesla at the plasma center of 1.1m and the maximum field at the conductor is 5.1 Tesla. The TF coils are D-shaped and 16 numbers of them are deployed symmetrically around the torus. The winding pack for each TF coil consists of 6 double pancakes with each pancake having 9 turns. The winding pack 2.07 m in height by 1.5 m in width at mid-plane with it s cross-section 147 mm by 199 mm. The forces experienced by the winding are transferred to the coil casing which is shrunk fit to the winding pack. The centering forces on the TF coils are supported by nosing the coils cases while the out-of-Plane forces on the coils are supported by inter-coil structure. The Dead weight of the TF Magnet assembly is supported at the bottom.

The paper describes the supporting system for the TF magnet coils. Results of the stress analysis of the support structure, carried out using ANSYS will be discussed including optimization of the supports for the critical loading conditions and minimization of conduction heat loss to the cold mass.